ML17304B143

Forwards Corrections to Reload Analysis Rept for Unit 3, Cycle 2.Info Reflects Necessary Changes for Revised end-of-cycle 1 Termination Burnup of 397 EFPD

ML17304B143
Person / Time
Site:	Palo Verde
Issue date:	04/26/1989
From:	Karner D ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
161-01866-DBK-J, 161-1866-DBK-J, NUDOCS 8905090334
Download: ML17304B143 (22)

Text

{{#Wiki_filter:A.C CK1KRATED DIR1BUTION DEMONSTJTIOY SYSI'EM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR-8905090334 DOC.DATE: 89/04/26 NOTARIZED: NO DOCKET FACIL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530-AUTH.NAME AUTHOR AFFILIATION KARNER,D.B. Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards'orrections to reload analysis rept for Unit 3, Cycle 2. DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE-TITLE: OR Submittal: General Distribution NOTES:Standardized plant. 05000530 g RECIPIENT ID CODE/NAME PD5 LA DAVIS,M.J. INTERNAL: ACRS NRR/DEST/CEB 8H NRR/DEST/ICSB NRR/DEST/RSB 8E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: LPDR NSIC NOTES COPIES LTTR ENCL '1 1 5 5 6 6 1 1' 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD DAVIS,M NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MTB 9H NRR/DOEA/TSB 11 RE F LE 01 NRC PDR COPIES LTTR ENCL 1 1 5 5 1 1 1 1 1 1 1 1 0 1 1 1 1 R I NOTE 'ZO ALL "RIDS" RECIPIENIS PIZASE HELP US 'ZO REDUCE WASTE! CDFZACZ 'IHE DOCUMEM7 CXÃZROL DESK, ROOM Pl-37 (EXT. 20079) KO ELIMINATE KR3R NME FRY DISTRIBUTION LISTS FOR DOCUMENIS YOU DON'T-NEEDf S h 'D D S TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL 32

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Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX. ARIZONA85072-2034 161-01866-OBK/J RP April 26, 1989 Docket Nos. STN 50-530 Document Control Desk U.. S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D. C. 20555

Reference:

APS'etter from D. B. Karner to USNRC; 161-01575-DBK/PGN, dated 12/27/88'.

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Unit 3 Corrections to Reload Analysis Report for Unit 3, Cycle 2 File: 89-G-056-026 Attached are revised pages to the final PVNGS Unit 3, Cycle 2'eload Analysis Report.(RAR) transmitted in the reference. These pages reflect the necessary changes for the revised end-of-cycle 1 termination burnup of 397 EFPD. All current RAR analyses remain valid and bound the 397 'EFPD end-of-cycle. burnup. Additionally, please find the revised pages which reflect the transmittal of the letters of'pplicability of Section 12 references questioned by your staff. This transmittal documents all changes to the final Unit 3, Cycle 2 RAR in support of the startup of Cycle 2. .Should you have any questions, please call. Yours very truly,, D. B'. Karner Executive Vice Presi;dent DBK/NLT/hw Attachments cc,: G. W. Knighton (all w/a) M. J. Davis J. B. 'Martin T. J. 'Polich pDR ~DO pDC 89050 DOCK 05000530 90 3P 890426 p

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Document Control Desk Page 2 161-01866-DBK/J RP April 26, 1989 bcc: P. F. Crawley N. L. Turley W. B. Miller R. A. Bernier A. C. Rogers W. F. Quinn

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INTRODUCTION AND

SUMMARY

This report provides an evaluation of the design and performance of palo Verde. Nuclear Generating Station Unit 3 (PVNGS-3) during its second cycle of operation at 100K rated core power of 3800, MMt and NSSS power of 3822 MNt. Operating conditions for Cycle 2 have been assumed to be consistent with those of the previous cycle and are summarized as full power operation under,,base load conditions. The core will consist of irradiated Batch B and C assemblies, along"with fresh Batch D a -emblies. The Cycle 1 termination burnup has been assumed to be between '397. and 420 EFPD (effective full power days). The first cycle of operation will hereafter .be referred to in this .report as, the "Reference Cycle."'he safety criteria (margins of safety, dose limits, etc.) applicable for the plant were established in Reference 1-1'. A review of all postulated accidents and anticipated operational occurrences has shown that the Cycle 2 core design meets these safety criteria. The Cycle 2 reload core characteristics have been evaluated with respect to the Reference Cycle. Specific differences in core fuel loadings have been accounted for in the present analysis. The status of the postulated accidents and anticipated operational occurrences for Cycle 2 can be summarized as follows: 1. Transient data are less severe than those of the Reference Cycle analysis; therefore, no reanalysis is necessary, or 2. Transient data are not bounded by those of the Reference Cycle

analysis, therefore, reanalysis is required.

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2.0 OPERATING HISTORY OF THE REFERENCE CYCLE The plmt is currently in its first fuel cycle which began with initial criticality on October 25, 1987. Power Ascension began on October 28,

1987, and on January 7,

1988, the.unit was declared in commercial operation. It is presently estimated that Cycle 1 will terminate on or about March 3, 1989. The Cycle 1 termination point can vary between 397 and '420. EFPD to accommodate the plant schedule and'till be within the assumptions of the Cycle 2 analyses. 2-1'

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5.0 NUCLEAR DESIGN 5.1 PHYSICS CHARACTERISTICS 5.1.1 Fuel Management The Cycle 2 core makes use of a low-leakage fuel management

scheme, in which previously burned Batch B assemblies are placed on the core periphery.

Most of the fresh Batch D assemblies are located throughout the interior of the core where they are mixed with the previously burned fuel in a pattern that minimizes power peaking. With this loading and a Cycle 1 endpoint at 410 EFPD, the Cycle 2 reactivity lifetime for full power operation is expected to be 410 EFPD. Explicit evaluations have been performed to assure applicability of all analyses to a Cycle 1 termination burnup of between 397-420 EFPD and for a Cycle 2 length up to 420 EWPD. Characteristic physics parameters for Cycle 2 are compared to those of the Reference Cycle in Table 5-1. The values in this table are intended to represent nominal core parameters. Those values used in the safety analysis (see Sections 7 and 8) contain appropriate uncertainties, or incorporate values to bound future operating

cycles, and in all cases are conservative with respect to the values reported in Table 5-1.

Table 5-2 presents a summary of CEA reactivity worths and allowances for the end of Cycle 2 full-power steam line break transient with a comparison to the Reference Cycle data. The full power steam line break was chosen to illustrate differences in CEA reactivity worths for the two cycles.

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Letter, A.

E. Lundvall, Jr. to J. R. Miller (Chief Operating Reactors Branch f3), "Calvert Cliffs Nuclear Power Plant Unit Hos. I and 2, =Docket Nos. 50-317 and 50-318, Request for Amendment", December 31, 1984. (4-3) EPRI HP-3966-CCM,. "CEPAN Method of Analyzing Creep Collapse of Oval Cladding Volume '5: Evaluation of, Interpellet Gap Formation and Clad Collapse i'n Modern PWR F 'el Rods," April, 1985. (Letter from D. B. Karner, APS to USNRC; 161-01867-JRP/DBK, April 26, 1989). "Safety Evaluation by the Office,of 'Huclear Reactor Regulation Related to Amendment Ho. 104 to Facility Operating License Ho. DPR-53, Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant Unit No. 1 Docket Ho. 50-317",

May, 1985.

(4-5) CEHPD-}39-P-A, "C-E Fuel Evaluation Model,",July,, 1974. (4-6) CEH-}6}(B)-P, "Improvements to Fuel Evaluation Model,."

July, 1981.

(4-7) R. A. Clark (HRC) to A. E. Lundvall,. Jr. (BGLE), "Safety Evaluation, of CEH-}61 (FATES3)," March 3}, 1983. (4-8) "Combustion Engineerino Stan'dard Safety Analysis Report (CESSAR)", Docket -:STH-50-470F. (4-9) "Palo Verde Nuclear Generating Sta ion Unit Ho. }, F.inal. Safety Analysis Report," Arizona Public Service

Company, Docket Ho. 50-528, Section 4.2.4.

(4-10) CESSAR

SSER2, Section 4.2.5, "Guide Tube Wear Surveillance".

12-2

Ot k ~,

(4-11) 161-00730-EEVB/LJM, "Final 'Surveillance Test Results for PVNGS-1 Cycle 1," January 8, 1988. (4-12) J. G. Haynes (ANPP) to Document Control Desk (NRC), "Fuel Assembly Guide Tube Wear Program for PVNGS Unit 2," 161-00453-JGH/SGB, August 20, 1987. (4-13) 161-01102-EEVB/PGN, "Fuel Surveillance Test Results for PVNGS-2 Cycle 1." June 9, 1988. 12 ' SECTION

5.0 REFERENCES

(5-1) EPRI NP-3966-CCM, "CEPAN Method of Analyzing Creep Collapse of Oval Cladding, Volume 5: Evaluation of Interpellet Gap Formation and Clad Collapse in Modern PWR Fuel Rods " Aori 1 1985 (Letter from D. B. Karner, APS to USNRC; 16)-01867-3RP/DBK, April 26, 1989). (5-2) A. E. Lundvall (BGRE) to J. R. Miller (NRC), "Calvert Cliffs Nuclear Power Plant Unit 1; Docket No. 50-317 Eighth cycle License Application," February 22, 1985. (5-3) "Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 04 o Facili-y Operating License No. DPR-53', Baltimore Gas and Electric

Company, Calvert Cliffs Nuclear Power Plan Uni No. 1, Docket No. 50-317," May, 1985.

(5-4) CENPD-153-P, Rev., 1-P-A, "INCA/CECOR Power Peaking Uncertainty,"

May, 1980.

(5-5) CENPD-266-P-A, "The ROCS and DIT Compu:er Codes for Nuclear Design," April, '983. 12.6 SECTION 6.0 REFERENC S (6-1) CENPD-161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core", April, 1986. 12-3

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(6 2) CENPD-162"A, "Critical Heat Flux Correlation for C-E Fuel Assembl,ies with Standard Spacer 'Grids, Part 1, Uniform Axial Power Distribution," September, -1976. (6-3) (6-4) CEH-160-{S)-, Rev. 1-P', "CETOP Code Structure and Modeling Methods for San ONofre Nuclear Generating 'Station Units 2 and 3", September, 1981. (Letter from D. B. Karner; APS to USNRC; 161'-01867-JRP/DBK, April 26, 1989). CEH-356(V).-P-A,. Rev. 01-P-A,, "Modified; Statistical Combination of Uncertainties",

Nay, 1988.

(6-5) Enclosure 1-P to LD-82-054, "Statistical Combination of System Parameter Uncertainties in Thermal Margin, Analyses for System 80", submitted by letter from A. E. Scherer (C-E) to D. G. Eisenhut (NRC), May 14, 1982. ( -6) CESSAR SSER 2 Section 4.4.6, Statistical Combination of Uncertainties. (6-.7,) CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983. SEC ION 7.0 R FERENCES (7-1) "Palo Verde Nuclear Generatina Station Unit No. , Final Safety Analysis Report," Arizona Public Service

Company, Docke'o.

50-528. (7-2) "CESSAR, Combustion Enaineering Stancard Safety Analysis Report." Docket No. 50-470. (7-3) "Standard Review Plan," NUREG-0800,.Rev. 2, 1981. (7-4) "CESEC, Digi-al Simuia-ion o, a Combustion =nginee".,ing Nuclear Steam Supply System" December '98 , Enclosure 1-P to LD-82-001 January 6, 1982. 12-4

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(7-5) R. V. Macbeth, "An Appraisal of Forced Convection Burnout Data," Proc. Instr. Mech. Engrs., Vol. 180, Pt. 3C, PP 37-50, 1965-1966 '7-6) D. H. Lee, "An Experimental Investigation of Forced Convection Burnout in High Pressure Mater - Part IV, l.arge Diameter Tubes at about 1600 psia," A.E.E.M. Report R479, 1986. (7-7) CEH-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cli.fs 1 and 2," December 1981. (<<tter from D. B. Karner; APS to USNRC; 161-01867-JRP/DBK, Apri126, 1989). (7-8) CEH-308-P-A, Revision OO-P, "CPC/CEAC software Modifications for the CPC Improvement Program," April, 1986. (7-9) CEHPD-188-A, "HERMITE Space-Time Kinetics," July, 1975. (7-10) CEHPD-161-P, "TORC Code A Computer Code for Determining the Thermal Margin of a Reactor Core," July 1975. (7-ll) CEHPD-ZOO-P, "TORC Code Yerifica ion and Simplified Modeling Methods," January 1977. '(7-12) CEHPD-183, "Loss of Flow - C-E Methods =or Loss o; Flow Analysis," July 1975. (7-13) CEHPQ-199-P-A, Rev. 1-P, "CE Setpoint Methodolooy,"

January, 1986.

(7-14) Safety Evaluation by the office of Nuclear Reactor Reaulation Supporting Amendment Ho. 47 to HPF-l0 and Amendment Ho. 36 to HPF-15, Southern California Edison

Company, et. al.,

San Gnofre Generating 5:ation, Units 2 and 3.

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March 2, 1989 DISTRIBUTION t Docket File s'DR LPDR PD 5 JLee DOCKET'NO(S). STN 50-530 Hr. Donald B. Karner Executive Vice President Arizona Nuclear Power Project Post Office Box 52034 Phoenix, Arizona 85072-2034

SUBJECT:

ARIZONA PUBLIC SERVICE COMPANY~ ET AL PALO VERDE NUCLEAR'GENERATING-'STATION~ UNIT 3 The following documents concerning'our review of the subject facility are transmitted for your information. Noti ce of Recei pt of Applicati on, dated Draft/Final Environmental Statement, dated + Notice of Availability of Draft/Final,Environmental Statement, dated Safety Evaluation Report, or Supplement No. dated Environmental Assessment and Finding of No Significant Impact, dated Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating'icense, dated x Bi-Weekly Notice; Applications and Amendments to Operating Licenses Involving No Bg i d C id .d d~l (i] Exemption, dated Construction Permit No. CPPR- , Amendment.No. dated Facility Operating License No., Amendment No. dated Order Extending Construction Completion Date, dated Monthly Operating Report for, transmitted by letter dated Annual/Semi-Annual Report-transmi,tted by letter dated

Enclosures:

As stated Office of Nuclear Reactor Regulation cc: See next page 0FF1CE> SURNAME/ DATEP ~ ~ ~ ~ ~ ~ ~ iPD" 3/ 8 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ NRC FORM 318 110/801 NRCM 0240 OFFtCIAL RECORD COPY

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